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二维六角形轻水堆燃料组件中子通量分布的计算
引用本文:张颖,谢仲生,陈达,江新标.二维六角形轻水堆燃料组件中子通量分布的计算[J].核动力工程,2000,21(6):484-491.
作者姓名:张颖  谢仲生  陈达  江新标
作者单位:1. 西安交通大学,710049
2. 西北核技术研究所,西安,710024
摘    要:介绍利用穿透概率法求解二维六解形几何多群中子积分输运方程。子区内中子源及通量采用线性分布,子区表面通量在方向上采用简化6P1近似。根据提出的模型,编制了TPHEX-B程序,并对一些轻水堆六解形组件问题做了计算,计算结果与MC结果进行了比较,符合良好。本程序可用于六解形轻水堆燃料组件计算。

关 键 词:中子能量分布  六角形轻水堆  参数计算  燃料组件

Calculation of the Flux Distribution in Two Dimensional Hexagonal LWR Fuel Assembly
Zhang Ying,Xie Zhongshen,Chen Da,Jiang Xinbiao.Calculation of the Flux Distribution in Two Dimensional Hexagonal LWR Fuel Assembly[J].Nuclear Power Engineering,2000,21(6):484-491.
Authors:Zhang Ying  Xie Zhongshen  Chen Da  Jiang Xinbiao
Abstract:This paper describes the model of calculating the flux distribution in two dimensional hexagonal geometry LWR fuel assembly by transmission probability method.The source within the meshes is assumed to be isotropic and linearly dependent on x and y coordinates.At the mesh surfaces the const space distribution and the simplicity 6P1 approximation for the anisotopic angular distribution are considered.Based on proposal model,the code TPHEX- B is encoded and some hexagonal light water reactor assembly problems have been tested.The calculated results are compared with those of MC method.They are all in good agreement.The code TPHEX- B can be used to the hexagonal geometry assembly calculation of LWR.
Keywords:Transmission probability Hexagonal geometry Assembly Neutron flux
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